Published September 2008 | Version v1
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Characterization of Factors affecting IASCC of PWR Core Internals

Creators

  • 1. Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

Description

A lot works have been performed on IASCC in BWR. Recent efforts have been devoted to investigate IASCC in PWR, but the mechanism in PWR is not fully understood yet as compared with that in BWR due to a lack of data from laboratories and fields. Therefore it is strongly needed to review and analyse recent researches of IASCC in both BWR and PWR for establishing a proactive management technology for IASCC of core internals in Korean PWRs. This work is aimed to review mainly recent technical reports on IASCC of stainless steels for core internals in PWR. For comparison, the works on IASCC in BWR were also reviewed and briefly introduced in this report

Availability note (English)

Available from INIS in electronic form; Also available from KAERI

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Additional details

Publishing Information

Imprint Pagination
79 p.
Report number
KAERI/AR--811/2008

INIS

Country of Publication
Korea, Republic of
Country of Input or Organization
Korea, Republic of
INIS RN
40068015
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S36: MATERIALS SCIENCE;
Descriptors DEI
BWR TYPE REACTORS; CRACKING; PWR TYPE REACTORS; RADIOLYSIS; REACTOR CORES; STAINLESS STEELS; STRESS CORROSION
Descriptors DEC
ALLOYS; CARBON ADDITIONS; CHEMICAL RADIATION EFFECTS; CHEMICAL REACTIONS; CORROSION; DECOMPOSITION; ENRICHED URANIUM REACTORS; HIGH ALLOY STEELS; IRON ALLOYS; IRON BASE ALLOYS; POWER REACTORS; PYROLYSIS; RADIATION EFFECTS; REACTOR COMPONENTS; REACTORS; STEELS; THERMAL REACTORS; THERMOCHEMICAL PROCESSES; TRANSITION ELEMENT ALLOYS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Notes
65 refs, 42 figs, 3 tabs